47,020 Matching Results

Search Results

Advanced search parameters have been applied.

Augmented Reality Tour of Campus

Description: Poster for the 2018 International Conference on Knowledge Management. This poster describes a new approach to the standard campus tour by using an augmented reality campus application.
Date: November 9, 2018
Creator: Colvin, Erin; Cho, Inyoung; Donnelly, Trevor; Le, Nguyen & Naquib, Moustafa
Partner: UNT College of Arts and Sciences

Source Preferences in Everday Life Information Seeking

Description: Poster for the 2018 International Conference on Knowledge Management. This poster uses a questionnaire to identify which information sources respondents would use in specific situations and which qualities of those sources were most important to them.
Date: November 9, 2018
Creator: Dill, Emily Anne; Le, Kimdy & Poulsen, Joan
Partner: UNT College of Arts and Sciences

Systems analysis of instrumentation for in situ examination of rock properties. Final report. [Telemetered instrumentation for monitoring buried nuclear waste]

Description: If salt beds or shale beds are used for burial of nuclear wastes, then boreholes that penetrate the beds will be sealed to prevent transport of water into the beds via the boreholes. There will be interest in monitoring the environment in local regions of the borehole for years to come. Such monitoring may be aimed at providing assurance that the integrity of the borehole plug and the integrity of borehole wall seals have not degraded. Of course, there will be interest in monitoring the burial vault geology as well, and the results of this study are relevant to this requirement also. A study of buried instrumentation in boreholes without any wires between the buried instruments and the surface of the earth was performed. Consequently, buried power supplies and through-the-earth communications systems are required. Study ground rules included the following: burial depths to range between 150 m and 1500 m; maximum temperature of 100/sup 0/C at the burial depth; and system target lifetime of 10 to 100 years. The instrumentation system is separable into four functional subsystems: (A) a basic instrument subsystem; (B) a command, control, and data processing (CCD) subsystem; (C) a communication subsystem; and (D) a power supply subsystem. The major findings of the study are listed by subsystem. (WHK)
Date: October 1, 1976
Partner: UNT Libraries Government Documents Department

Project characteristics monitoring report: BWIP (Basalt Waste Isolation Program) repository project

Description: This monitoring report has been prepared to show compliance with provisions of the Nuclear Waste Policy Act of 1982 (NWPA) and to provide local and state government agencies with information concerning the Basalt Waste Isolation Program (BWIP). This report contains data for the time period May 26, 1986 to February 1988. The data include employment figures, salaries, project purchases, taxes and fees paid, worker survey results, and project closedown personal interview summaries. This information has become particularly important since the decision in December 1987 to stop all BWIP activities except those for site reclamation. The Nuclear Waste Policy Amendments Act of 1987 requires nonreclamation work at the Hanford Site to stop as of March 22, 1988. 7 refs., 6 figs., 28 tabs.
Date: March 1, 1988
Creator: Friedli, E. A.; Herborn, D. I.; Taylor, C. D. & Tomlinson, K. M.
Partner: UNT Libraries Government Documents Department

Interim storage of spent fuel assemblies

Description: Spent fuel discharged from light water reactors (LWR) is cooled at the reactor sites for at least 5 months to allow short-lived radioactive isotopes to decay. Recently, spent fuel has been considered as a possible waste form suitable for interim storage or even ultimate disposal. Several alternatives have been demonstrated or proposed for retrievable storage of spent fuel for periods of up to 100 years. These include storage in water-cooled basins, air-cooled vaults, concrete surface silos, geologic formations, or near-surface heat sinks. Water-cooled storage of spent fuel in near-surface cells of heavily reinforced concrete lined with stainless steel has been proven by about 30 years of operating experience at reactor sites and fuel reprocessing plants. Near-surface storage with forced-draft air cooling of HTGR (High Temperature Gas Reactor) fuels is being used by INEL (Idaho National Engineering Laboratory) and is feasible for unpackaged LWR fuel that has been out of the reactor at least 3 to 4 years. Natural-draft cooling of spent fuel has also been proposed, and demonstration programs are in progress for CANDU (Canada Deuterium Uranium) fuel. Spent fuel assemblies are sealed in thick low-carbon steel containers and placed in large cylindrical concrete housings (silos) located outdoors. The cooling is completely passive, requiring little maintenance and only minimal surveillance. Recent studies comparing the economics of interim storage of spent fuel (throwaway fuel cycle) with prompt chemical reprocessing conclude that disposal as fuel decreases the Nation's natural resources significantly and is not cost justified if both plutonium and uranium are recycled in the nuclear fuel cycle.
Date: January 1, 1976
Creator: King, F. D. & Baker, W. H.
Partner: UNT Libraries Government Documents Department

Fixation of Hanford sludge by conversion to glass

Description: Redox and Purex process sludges stored at Hanford can be converted to durable borosilicate glasses by melting at 1100--1400/sup 0/C charges containing 30 to 40 weight percent washed, dried sludge, 45 to 60 weight percent SiO/sub 2/, 5 to 15 weight percent B/sub 2/O/sub 3/, 0 to 10 weight percent Na/sub 2/O, 0 to 5 weight percent Li/sub 2/O, and 0 to 5 weight percent TiO/sub 2/. Leach rates in deionized water (25/sup 0/C) for the glasses range from about 10/sup -7/ to 10/sup -5/ g/cm/sup 2/-day.
Date: March 1, 1977
Creator: Kupfer, M. J. & Schulz, W. W.
Partner: UNT Libraries Government Documents Department

United States program for the safety assessment of geologic disposal of commercial radioactive wastes

Description: The safe disposal of commercial radioactive wastes in deep geologic formations is the goal of the National Waste Terminal Storage (NWTS) Program. A comprehensive safety assessment program has been established which will proceed on a schedule consistent with the start-up of two waste repositories in late 1985. Safety assessment begins with selection of a disposal site; that is, all geologic and hydrologic factors must indicate long-term stability of the formation and prospective isolation of wastes from circulating around waters for hundreds of thousands of years. The long-term stability of each site must be demonstrated by sophisticated rock mechanics analyses. To help provide answers on the mechanism and consequences of an unlikely breach in the integrity of the repository, a Waste Isolation Safety Assessment Program (WISAP) is being sponsored at the Battelle Pacific Northwest Laboratories. Methods and data necessary to characterize the safety of generic geological waste disposal concepts, which are to be applied in the assessment of specific sties, will be developed. Other long-term safety-related studies that complement WISAP are in progress, for example, borehole plugging, salt dissolutioning, and salt transport in vertical boreholes. Requirements for licensing are in the process of being formulated by the NRC.
Date: January 1, 1977
Creator: Claiborne, H. C.
Partner: UNT Libraries Government Documents Department

Conceptual design criteria for facilities for geologic disposal of radioactive wastes in salt formations

Description: The facility design requirements and criteria discussed are: general codes, standards, specifications, and regulations; site criteria; land improvements criteria, low-level waste facility criteria; canistered waste facility criteria; support facilities criteria; and utilities and services criteria. (LK)
Date: January 1, 1977
Partner: UNT Libraries Government Documents Department

Freeze block testing of buried waste lines

Description: An investigation was conducted to demonstrate application of freeze blocking in waste transfer lines such that a hydrostatic pressure test can be applied. A shop test was conducted on a 20-foot length, 3-inch schedule 40, carbon steel pipe using a coolant of dry ice and Freon. The positive results from these tests prompted a similar employment of the freeze block method in hydrostatic pressure testing the feed inlet leading to 241-S-101 Waste Tank. This pipeline is a 3-inch schedule 10, stainless steel pipe approximately 800 feet long. The freeze block was formed near the lower end of the pipe as it entered the 101-S Waste Tank and a pressure hold test was applied to this pipeline. This test proved the integrity of the pipeline in question, and demonstrated the validity of freeze blocking an open-ended pipeline which could not be hydrotested in other conventional ways. The field demonstration facility, costing $30,200 was completed late in 1975.
Date: May 20, 1976
Creator: Robbins, E. D. & Willi, J. C.
Partner: UNT Libraries Government Documents Department

High level waste canister emplacement and retrieval concepts study

Description: Several concepts are described for the interim (20 to 30 years) storage of canisters containing high level waste, cladding waste, and intermediate level-TRU wastes. It includes requirements, ground rules and assumptions for the entire storage pilot plant. Concepts are generally evaluated and the most promising are selected for additional work. Follow-on recommendations are made.
Date: September 1, 1975
Partner: UNT Libraries Government Documents Department

Airborne effluent control at fuel enrichment, conversion, and fabrication plants

Description: Uranium conversion, enrichment, and fuel fabrication facilities generate gaseous wastes that must be treated prior to being discharged to the atmosphere. Since all three process and/or handle similar compounds, they also encounter similar gaseous waste disposal problems, the majority of which are treated in a similar manner. Ventilation exhausts from personnel areas and equipment off-gases that do not contain corrosive gases (such as HF) are usually passed through roughening and/or HEPA filters prior to release. Ventilation exhausts that contain larger quantities of particles, such as the conversion facilities' U/sub 3/O/sub 8/ sampling operation, are passed through bag filters or cyclone separators, while process off-gases containing corrosive materials are normally treated by sintered metal filters or scrubbers. The effectiveness of particle removal varies from about 90 percent for a scrubber alone to more than 99.9 percent for HEPA filters or a combination of the various filters and scrubbers. The removal of nitrogen compounds (N/sub 2/, HNO/sub 3/, NO/sub x/, and NH/sub 3/) is accomplished by scrubbers in the enrichment and fuel fabrication facilities. The conversion facility utilizes a nitric acid recovery facility for both pollution control and economic recovery of raw materials. Hydrogen removal from gaseous waste streams is generally achieved with burners. Three different systems are currently utilized by the conversion, enrichment, and fuel fabrication plants to remove gaseous fluorides from airborne effluents. The HF-rich streams, such as those emanating from the hydrofluorination and fluorine production operations of the conversion plant, are passed through condensers to recover aqueous hydrofluoric acid.
Date: January 1, 1976
Creator: Mitchell, M. E.
Partner: UNT Libraries Government Documents Department

National Waste Terminal Storage Program information meeting, December 7-8, 1976. [Slides only, no text]

Description: Volume I of the report comprises copies of the slides from the talks presented at the first session of the National Waste Terminal Storage Program information meeting. The agenda for the first day included an overview of the program plus presentations on such subjects as schedules and controls, facility projects, systems studies, regulatory affairs and technical support. (LK)
Date: December 1, 1976
Partner: UNT Libraries Government Documents Department

Laser Raman spectrometric determination of oxy-anions in nuclear waste materials

Description: Oxy-anions in complex nuclear process-waste materials are being determined by laser Raman spectrometry (LRS). The double internal-standard technique developed by Marston is applied to the simultaneous determination of up to x anions in alkaline solutions. The method of Marston has been extended to solutions prepared from the solids formed in nuclear waste storage tanks. As many as six anions, aluminate, chromate, nitrate, nitrite, phosphate, and sulfate, are simultaneously determined in about one hour. Carbonate may also be determined, but in the presence of the prevalent nitrate, a chemical separation is required. Individual methods have been relegated to a secondary status due to the many advantages of LRS. Advantages such as small sample size, speed of analysis, accuracy, and specificity will be discussed. The typical precision obtained for analyses in high concentration is around five percent relative standard deviation.
Date: March 1, 1977
Creator: Miller, A. G.
Partner: UNT Libraries Government Documents Department

Project control support services for the National Waste Terminal Storage Program

Description: The Boeing Engineering and Construction Company has the responsibility to recommend and assist in designing and implementing a project control system for the Office of Waste Isolation. BEC, after analysis of the OWI management structure and techniques utilized, has recommended the implementation of a Program Control System (PCS) for use by OWI. This system embraces the scope of management needs for visibility and control of cost and schedule performance as well as providing a framework for all the various segments of a complete program control system. Because of the schedule constraints placed on OWI by DOE it was not deemed practical to implement all segments of PCS but rather those that are basic to the concept and can return the greatest short-term benefit. The area of cost and schedule control appears to provide the greatest benefit when combined with the control room techniques for visibility and control. Technical performance is not covered in this report. The segment of PCS titled Integrated Cost/Schedule (IC/S) was used to identify those functions unique to cost and schedule control.
Date: December 1, 1977
Partner: UNT Libraries Government Documents Department

Public comments and Task Force responses regarding the environmental survey of the reprocessing and waste management portions of the LWR fuel cycle

Description: This document contains responses by the NRC Task Force to comments received on the report ''Environmental Survey of the Reprocessing and Waste Management Portions of the LWR Fuel Cycle'' (NUREG-0116). These responses are directed at all comments, inclding those received after the close of the comment period. Additional information on the environmental impacts of reprocessing and waste management which has either become available since the publication of NUREG-0116 or which adds requested clarification to the information in that document.
Date: March 1, 1977
Partner: UNT Libraries Government Documents Department

Data input manual for RSI/TEVCO: a thermo/viscoelastic finite element computer program

Description: RSI/TEVCO is a plane finite element code designed to analyze elastic, thermoelastic, viscoelastic, or thermoviscoelastic problems. The basic element is the eight noded isoparametric quadrilateral element, but a six noded subparametric triangular element may be used separately or for gradation purposes with quadrilateral elements.
Date: February 1, 1977
Creator: Callahan, G. D. & Fossum, A. F.
Partner: UNT Libraries Government Documents Department

Volume reduction system for solid and liquid TRU waste from the nuclear fuel cycle: January--March 1977. [Ash immobilization]

Description: Facilities generating radioactive waste and a fuel processor were contacted to obtain data on types and quantities of waste produced. The incinerator is being modified to allow the burning of liquid wastes. Ash immobilization studies continued with both glass and cement being tested for rendering the ash inert. A drum compactor fabricator has been located who can compress drums to meet program requirements.
Date: July 27, 1977
Creator: Luthy, D. F. & Bond, W. H.
Partner: UNT Libraries Government Documents Department

Linear free energy relationships in glass corrosion

Description: Various theoretical models that have been proposed to correlate glass durability to their composition for a wide variety of silicate, borosilicate, and aluminosilicate glasses are examined. Comparisons are made between the predictions of these models and those of an empirical formulation extracted from existing data in the present work. The empirical approach provides independent confirmation of the relative accuracy of the silica release rate predictions of the different theoretical models in static leaching systems. Extension of the empirical approach used in this work are discussed. 23 refs., 2 figs., 1 tab.
Date: January 1, 1988
Creator: Abrajano, T. A. Jr.; Bates, J. K. & Bohlke, J. K.
Partner: UNT Libraries Government Documents Department

Fusion reactor radioactive waste management

Description: Quantities and compositions of non-tritium radioactive waste are estimated for some current conceptual fusion reactor designs, and disposal of large amounts of radioactive waste appears necessary. Although the initial radioactivity of fusion reactor and fission reactor wastes are comparable, the radionuclides in fusion reactor wastes are less hazardous and have shorter half-lives. Areas requiring further research are discussed.
Date: August 26, 1976
Creator: Kaser, J. D.; Postma, A. K. & Bradley, D. J.
Partner: UNT Libraries Government Documents Department

Management of radioactive low level liquid, gaseous, and solid wastes in the 200 areas

Description: The practices which are currently used for handling radioactive waste are outlined. These include burial of solid waste, scrubbing of off gas streams, and routing liquid effluents (mostly cooling water) to open ponds where the water percolates to the water table. (LK)
Date: June 24, 1976
Creator: White, A. T.
Partner: UNT Libraries Government Documents Department